The effect of temperature on the properties of graphite is being determined by exposing samples to pile neutrons at controlled temperatures in the range 75 C to 225 C. The first series of samples were charged into the newly installed dry, water-cooled test channel at B pile on January 23, 1951. This report presents details of the charging operation and observations noted during the initial operation of the test.

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As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amount in order to decrease the emergency steam demands and keep the combined steam demands of 100-B and 100-C Areas within the capacity of 184-B Boiler House, as outlined in Document HDC-2106, revised June 4, 1951. This report recommends that the desired results be obtained by simply reducing the speed setting of the turbine speed governors. No new equipment is needed. The setting of the emergency over speed trips would be left unchanged.

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Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentration step has been modified to permit the greater capacity. At 600 MWD/T (522 g/t) then, the 112 tons uranium per month capacity limits the plutonium output of the plant to 58.5 Kg per month at 80% operating efficiency. The remaining 38 Kg plutonium per month may be processed in the B and T BiPO{sub 4} plants at an operating efficiency of 89.5%; if this operating efficiency cannot be realized, the postulated production rate may be met by either an increased Redox efficiency or by accepting an increased plutonium waste loss of 1% on some portion of the BiPO{sub 4} production.

It is the purpose of this document to record the significant steps in the removal of a ruptured slug from tube {number_sign}2562-H.

This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which they are primarily interested.

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This document describes the scope of the C-431-B Reactor Production Facility. In dealing with the broad phases of the project, it includes the Sections ``A`` (Scope Modifications) of the approved Design Criteria, modified to ensure correctness to date. Location of the facility has been set as shown on the site map in HDC-2101, designated site number one. Included in Project C-431-B are the 105-C Building, including within that building facilities previously located in the 1608 Building, a contaminated effluent crib adjacent to 105-C, and gas facilities using the 115-B Building interconnected with 105-C. Also included are an oil shed, a thimble storage cave, a badge house, and an exclusion fence. Building services and process lines will be considered part of the project to a location nominally five feet outside of 105-C.

The {open_quotes}O{close_quotes} ring seal has been proposed to replace the van stone flange and the bellows thermal expansion assembly currently used on the existing Hanford piles to achieve water and gas seals, respectively. Possible advantages of the {open_quotes}O{close_quotes} ring seal are: (1) simplification of component parts and elimination of van stone corrosion; (2) simplification of maintenance; (3) lower costs of initial erection; (4) increased strength. This test supplements Test Project No. 27 (a preliminary thermal cycling test) in applying the {open_quotes}O{close_quotes} ring seal assembly to actual pile operating conditions.

Mechanization of the 300 Area slug canning facilities is required to obtain uniform high quality product and to eliminate variables introduced by the human element. The work to be covered by this brochure will cover requirements for mechanization of only the operations occurring within the aluminum-silicon canning bath: can and cap preheating and wetting, canning assembly, and quenching operation. Briefly, this machine will be required to insert a prepared uranium slug into an aluminum can and close the can opening with an aluminum cap. All assembly operations are to be carried out underneath a molten bath of aluminum-silicon bonding alloy. The uranium slug is preheated and prewetted before being transferred to the assembly furnace; however, the process must be so timed that proper preheating and wetting is attained before the slug is inserted. After assembly the completed canned slug is transferred to the quenching station, where the components are to be firmly held together until the molten Al-Si has frozen, forming a homogeneously bonded assembly.

This is a progress report of the production reactors on the Hanford Reservation for the month of May 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This is a progress report of the production reactors on the Hanford Reservation for the month of April 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

The 100-C project is to be located adjacent to the present 100-B Area. It is planned to build an addition to the present 181-B river pump house using the same elevations for pump settings, intakes, and floors as for the present pump house, thus maintaining the same suction conditions and flood protection as B Area. The 105 Building will be located on higher ground than B Area and therefore, protection against possible flood damage is assured. This report is divided into the following sections: (1) general description of project; (2) addition to existing river pump house; (3) raw water lines from 181-B addition to 183-C lead house; (4) the 183-C filter plant; (5) 190-C process pump house; (6) power house addition; (7) high tanks; (8) retention basins; (9) outside streamlines; (10) primary substation; (11) outside underground lines; (12) outside electric lines; (13) roads, railroads, walks, fences; (14) structural design of all buildings; and (15) architectural design of all buildings.

This document presents a summary of work and progress at the Hanford Engineer Works for October 1951. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

This is a progress report of the production reactors on the Hanford Reservation for the month of August 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

Project C-431-A includes the design of the C Water Plant outfall structure. This report documents design assumptions and the design of the spillway, outfall sewers, spillway chute, trash racks, walkways, stop log and trash rack slots, main sewer, and retention sewers. The spillway capacity is to be 268,000 gpm with a crest elevation at 429.0. This flow capacity is composed of flow from the 105-C Retention Basin (80,000 gpm), 105-B Retention Basin (45,000 gpm), and the 190-C Area main sewer (143,000 gpm).

Authorization has been received in the form of Modification No. 5 to Directive HW-158, dated March 23, 1951 to provide the necessary equipment and piping in the currently planned UO{sub 3} plant to permit the segregation of UO{sub 3} arising from the processing of stored metal waste (TBP) from that arising from ``current`` pile operation (Redox). In anticipation of this, the S Division, Manufacturing Divisions, requested that a study be made of the feasibility and cost of providing facilities for such segregation. This report is the result of that study. It concludes that by providing additional liquid storage and handling equipment, the desired segregation can be accomplished at a cost estimated to be approximately $128,000. $106,500 would be for Construction and $21,500 for Engineering. The schedule for this work will be reflected in the forthcoming modification to the C-361 Project Proposal. The general method of operation is alternately to store and process solution from TBP and Redox. The solution from TEP will be of a composition equivalent to the formula UNH and will require five days each week to process in the decomposition pots. The solution from Redox is received as 60% UNH and is batch concentrated in the storage …

This is a progress report of the production reactors on the Hanford Reservation for the month of July 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This is a progress report of the production on the Hanford Reservation for the month of February 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This is a progress report of the production reactors on the Hanford Reservation for the month of March 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

This report presents the cold shakedown run for the UO{sub 3} plan. One complete batch conversion will be made in each of the eighteen Calcining Pots using unirradiated uranium food solution. The objectives of this series of conversions are as follows. A mechanical test of the conversion units; a shakedown of the unloading, pulverizing and material handling equipment; a functional test of the Nitro Acid Absorber system operating at approximately 5 to 20% of its design capacity; the determination of the optimum temperature and time cycle conditions for 60% UNH feed solution. These conditions may be based upon calcination of the initial charge of 60% UNH solution to form UO{sub 3}, in one pot; a confirmation of the calibration of instruments; and to provide operating experience and process know-how.

Operation, rehabilitation, and expansion of Hanford Works was undertaken by GE from Sept. 1946 to the end of 1950. As a result of engineering progress, graphite reactors continue to be the country`s primary source of plutonium in production quantities; at the end of 1950, the plutonium production rate from the Hanford reactors was 299% of the 1946 rate with a 67% increase in reactor facilities. Improvements to existing plant facilities and processes resulted in savings of $53.3 M; in addition, it would have been necessary, in order to produce the amount of Pu delivered through 1950, to have constructed facilities costing $225.4 M if the following improvements had not been made: an irradiation-stable uranium slug; annealing of graphite; increased operating power level of the reactors; and improved separation methods. Tritium production, health/safety, and community management are mentioned.

This is a progress report of the production reactors on the Hanford Reservation for the month of December 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.